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REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT

Description: General research and development are reported on watercooled and sodium- cooled reactors. Studies are also reported on reactor safety and nuclear technology. (For preceding period, see Report ANL-6253.) (W.L.H.)
Date: November 1, 1960
Creator: Hilberry, N.
Partner: UNT Libraries Government Documents Department

Design Criteria for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor

Description: Design criteria are presented for liquid-metal loop facilities for the Advanced Test Reactor. It was concluded that achievement of the design objectives could not be predicted with any high degree of confidence when utilizing the package loop concept based on the design philosophy of the PW-19 loop. (M.C.G.)
Date: July 1, 1962
Partner: UNT Libraries Government Documents Department

NaK FREE CONVECTION COOLED SHAFT FREEZE SEAL FOR SRE PUMPS

Description: An investigation was conducted to determine the feasibility of using an NaK free-convection-cooled shaft freeze seal on the SRE main sodium pumps. The use of sodium in this application instead of tetralin eliminates the carburization hazard present should the seal coolant-(tetralin) leak into the sodium system. Results and recommendations are included. (J.R.D.)
Date: June 18, 1959
Creator: Perez, F.
Partner: UNT Libraries Government Documents Department

2000 KILOWATT SODIUM TEST FACILITY. Project Description and Progress Reports, June 30, 1958 through September 30, 1959

Description: The design and construction work completed on the 2000-kw Sodium Teat Facility during the period from April 1958 to Oct. 1959 is described. The purpose of the facility project in to test models of equipment components which are to be used in a moltsn plutonium, sodiumcooled fast reactor. (D. L.C.)
Date: March 1, 1961
Creator: Whinery, L.A.
Partner: UNT Libraries Government Documents Department

PRELIMINARY RADIATION SURVEY OF THE SRE

Description: An investigation was conducted to determine radiation dosags rates associated with operation of the Sodium Reactor Experiment at 8.3 Mw. These values were extrapolated to full-power operation. Hadiation survey results are tabulated. (J.R.D.)
Date: September 18, 1957
Creator: Hale, J.P.
Partner: UNT Libraries Government Documents Department

A STUDY OF SODIUM FIRES

Description: A study of sodium fires was performed to obtain detailed information on their characteristics and behavior in order to develop techniques for preventing, containing, and combatting them. lnvestigation was made of the technology of sodium fires, design criteria for improving the fire resistance of equipment and installations using sodium as a coolant, extinguishing materials and procedures for fighting sodium fires, and the evaluation of protective equipment. (auth)
Date: October 15, 1960
Creator: Gracie, J.D. & Droher, J.J.
Partner: UNT Libraries Government Documents Department

AN EVALUATION OF MERCURY COOLED BREEDER REACTORS

Description: Under the New Reactor Concepts Evaluation Program sponsored by the United States Atomic Energy Commission. Advanced Technology Laboratories (a Division of American Radiator & Standard Sanitary Corporation) has undertaken am investigation of the technical feasibility and economic potential of the use of boiling mercury as a coolant for fast breeder reactors The investigation was performed between January 1, 1959, and October 31. 1959. This is the final report on that investigation and is submitted in compliance with the terms of the program authorization, Contract Number AT(04-3)-109, Project Agreement Number 4. (auth)
Date: October 31, 1959
Creator: Bradfute, J.O.; Battles, D.W.; Clark, G.S.; Corridan, R.E.; Gellenbeck, E.T.; Kavanagh, D.L. et al.
Partner: UNT Libraries Government Documents Department

Ten-Year Sodium-Reactor Development Program

Description: >A 10-year program of development and construction of large-scale, sodium-cooled reactors is summarized. The current state of development of the SGR and its associated components is sufficiently advanced to permit construction of economic plants within the 10-year period. Two advanced Sodium Reactor concepts are presented. A construction program involving two reactor experiments and two full-scale plants with a capacity of 550 Mwe, together with associated development, is estimated to cost 6 million. Of this amount approximately 06 million would be borne by the AEC and the remainder by power utility companies. Escalation and construction loan interest charges are included in these figures. The cost of power from the larger power plant would be approximately 6 mills/kw-hr, based on 1959 dollars. (auth)
Date: April 11, 1959
Partner: UNT Libraries Government Documents Department

STEAM GENERATOR PRELIMINARY DESIGN

Description: A conceptual study on design of sodium-cooled reactor steam generators was conducted. Included is a detailed description of the preliminary design and analysis, based on the use of known materials and existing methods of fabrication. (See also APAE-41 Vols. I and III.) (J.R.D.)
Date: February 28, 1959
Partner: UNT Libraries Government Documents Department

Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor

Description: Results of the design criteria work performed prior to the termination of work on the package concept for the liquid metal loop facilities for the Advanced Test Reactor are summarized. Based on the results of the criteria studies, it was concluded that achievement of the design objectives could not be predicted with any high degree of confidence when utilizing the package loop concept based on the design philosophy of the PW-19 loop. The characteristics of the loop are given along with design and development accomplishments for associated equipment. (N.W.R.)
Date: March 1, 1963
Partner: UNT Libraries Government Documents Department